US11250961B2 - Packaging for the transport and/or storage of radioactive materials, permitting easier production and improved heat conductivity - Google Patents

Packaging for the transport and/or storage of radioactive materials, permitting easier production and improved heat conductivity Download PDF

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US11250961B2
US11250961B2 US17/050,584 US201917050584A US11250961B2 US 11250961 B2 US11250961 B2 US 11250961B2 US 201917050584 A US201917050584 A US 201917050584A US 11250961 B2 US11250961 B2 US 11250961B2
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Prior art keywords
annular
package
wall
unitary
radiation protection
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US20210241932A1 (en
Inventor
Didier Vuillermoz
Mathieu Brounais
Patrice Puppetti
Florent Ferry
Nicolas Bueil
Amine Neffati
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TN International SA
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TN International SA
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Assigned to TN INTERNATIONAL reassignment TN INTERNATIONAL ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: BROUNAIS, Mathieu, BUEIL, Nicolas, FERRY, FLORENT, NEFFATI, Amine, PUPPETTI, Patrice, VUILLERMOZ, Didier
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F3/00—Shielding characterised by its physical form, e.g. granules, or shape of the material

Definitions

  • the present invention relates to the field of packages for the transport and/or storage of radioactive materials, e.g. nuclear fuel or radioactive waste assemblies.
  • radioactive materials e.g. nuclear fuel or radioactive waste assemblies.
  • the present invention relates to a package comprising at its periphery an external radiation protection shell.
  • This shell can be obtained by stacking unitary annular structures, as is for example known from document EP 2 041 753.
  • the axially stacked structures together define an external radial surface of the package, which is relatively easy to decontaminate and capable of meeting current decontamination requirements.
  • the axial alignment of the holes passing through the different structures makes it possible to form a plurality of axial cavities, each extending over the entire length of the shell. These cavities are then filled with the radiation protection material, which then takes the form of a plurality of axial radiation protection strips circumferentially distributed in the shell.
  • one object of the invention is a package for the transport and/or storage of radioactive materials, comprising the characteristics of claim 1 .
  • the invention thus proves advantageous in that it allows the preservation of an easy-to-decontaminate package external shell, made by the multiplicity of outer annular walls of the unitary structures, while improving heat conduction function by virtue of the radial heat conduction walls, which may show a more direct radial path.
  • the inner annular wall in contact with the package side body enables heat exchanges between this side body and the unitary annular structure to be improved, by virtue of a large contact surface area.
  • the integration of the inner annular wall into the unitary annular structure eliminates the need for a heat transfer plate to be fixedly assembled to the package side body between the same side body and the unitary annular structure.
  • This inner annular wall in addition to providing protection against gamma radiation, makes it easier to install and maintain radiation protection in the cavity by taking part in delimiting it.
  • the design provided greatly facilitates assembly of the external shell, as the formation of the cavities housing the radiation protection elements no longer requires an accurate angular indexing of the structures in relation to each other. Also, the radiation protection elements can advantageously be installed gradually, as the stacking of the unitary annular structures is carried out.
  • the improved quality control of the radiation protection particularly when the protection is cast in situ. Indeed, it is possible to have visual access to the radiation protection installed in its cavity associated therewith, before it is closed by installing the directly consecutive structure in the stack. This visual access can advantageously take place over the entire perimeter of the radiation protection. Thus, in the event of non-compliance, the protection can be upgraded or reinstalled before closing the cavity in which it is housed.
  • the invention has at least one of the following optional characteristics, taken alone or in combination.
  • Each unitary annular structure is as a single piece, which makes it possible to limit manufacturing costs while maintaining the desired functionalities for this unitary annular structure.
  • Said radiation protection element is a neutron protection element, and each unitary annular structure meets the following formula: 0.02 ⁇ n.E 1/ H ⁇ 0.3 with:
  • n.E1/H ratio the lower the maximum temperature observed in the neutron protection elements. This ratio is thus higher than 0.02, while remaining below 0.3 in order to keep sufficient neutron protection.
  • the interval chosen for the n.E1/H ratio makes it possible to meet the thermal criterion, as well as the neutron protection criterion as a whole within the package, very satisfactorily.
  • the package also meets the following formula: n/H> 2 with “H” expressed in metres.
  • the thickness E1 of the radial heat conduction walls is limited, so that locally observed neutron leakage at these walls becomes advantageously reduced.
  • each unitary annular structure preferably meets the following formula: L/E 1 ⁇ 10 with “L” corresponding to the radial spacing between the inner and outer annular walls.
  • the thickness E1 of the radial heat conduction wall was a determining factor for the neutron dose-equivalent rate at 2 metres, by the way than the spacing L for which a threshold effect has also been detected, beyond which the increase in this spacing L no longer really affects the neutron dose-equivalent rate at 2 metres.
  • each unitary annular structure has a generally U-shaped half transverse cross-section, with the U-base formed by the radial heat conduction wall, and the two U-branches formed respectively by the outer and inner annular walls, the interior of the U forming the annular cavity housing said at least one radiation protection element.
  • the two free ends of both outer and inner annular walls lie in the same transverse plane of the package.
  • each unitary annular structure has, in a half transverse cross-section, the shape of a straight line segment, preferably oriented orthogonally to the central longitudinal axis.
  • the radial heat conduction wall of each unitary annular structure has, in a half transverse cross-section, at least one axial level change between a wall radially outer portion and a wall radially inner portion. Again, this provides better radiation protection, as no radial leakage occurs via the radial heat conduction walls.
  • the radiation protection element(s) forms a protective ring extending over 360°.
  • This ring extends continuously or discontinuously, and in the latter case obtained with several protective elements arranged end to end, circumferential overlapping areas are preferably provided at the junction between these elements.
  • each radiation protection element is an element cast in the cavity, or a prefabricated element arranged in the cavity.
  • At least several, and preferably all, of said unitary annular structures are identical. This allows for greater ease of manufacture.
  • the annular structures may have different geometries to adapt the volume of the annular cavities and the radiation protection housed therein to the local need for radiation protection.
  • Each unitary annular structure has a half transverse cross-section with a constant shape, still for ease of manufacture.
  • the radial heat conduction wall has the same thickness. This enables a uniform thermal performance to be provided in the radial direction.
  • the number of unitary annular structures is between 10 and 50, and the height of the external radiation protection shell formed by the stacking of these structures is between 1 and 4 m.
  • Another object of the invention is a method for manufacturing such a package for the transport and/or storage of radioactive materials; comprising the repetition of the following successive steps of:
  • Another object of the invention is a method for manufacturing such a package for the transport and/or storage of radioactive materials, comprising the repetition of the following successive steps of:
  • This implementation provides very easy assembly for the package components, by virtue in particular of the sequencing of steps and the possibility of manufacturing the radiation protection means separately from the package side body, or even at a different manufacturing site. It also allows easy verification of the compliance of the radiation protection elements, before installing the associated annular structure around the package side body. In the event of failure of one of the radiation protection elements, it can be upgraded or replaced, still before the associated installing annular structure around the side package body.
  • FIG. 1 represents a longitudinal axial cross-section view of a package for the storage and/or transport of radioactive materials, according to a preferred embodiment of the present invention
  • FIG. 1 a represents a transverse cross-section view of the package shown in FIG. 1 , along the line 1 a - 1 a of this figure;
  • FIG. 2 represents a perspective view of the package shown in FIG. 1 ;
  • FIG. 3 represents a partial perspective view of one of the unitary annular structures which form an external radiation protection shell of the package shown in the preceding figures;
  • FIG. 4 is a transverse cross-sectional view of the structure shown in FIG. 3 ;
  • FIG. 5 is a half transverse cross-sectional view of the unitary annular structure shown in FIGS. 3 and 4 ;
  • FIG. 6 schematically represents a method for manufacturing the package shown in the preceding figures, according to a first possible implementation
  • FIG. 7 schematically represents of a method for manufacturing the package shown in FIGS. 1 to 5 , with a second possible implementation
  • FIG. 8 shows part of the package shown in FIGS. 1 to 5 , according to one alternative embodiment
  • FIG. 9 shows a view similar to that of FIG. 5 , with the unitary annular structure being as one alternative embodiment
  • FIG. 10 is a partial perspective view of one of the unitary annular structures, according to yet another alternative embodiment.
  • FIG. 11 is a transverse cross-sectional view of the structure shown in FIG. 10 .
  • a package 1 for the storage and/or transport of radioactive materials such as nuclear fuel assemblies or radioactive waste (not represented) is represented.
  • This package 1 is shown in a vertical storage position, in which its longitudinal central axis 2 is vertically oriented. It rests on a package bottom 4 , opposite to a removable lid 6 along the height direction 8 , parallel to the longitudinal axis 2 . Between the bottom 4 and the lid 6 , package 1 has a side body 10 extending about the axis 2 and internally defining a housing 12 for radioactive materials.
  • This housing may form a containment enclosure 12 for the radioactive material, for example, arranged in a storage basket also located in the containment enclosure.
  • the containment enclosure is defined entirely by a canister, installed in the aforesaid housing 12 . The latter is closed axially upwards by the lid 6 and downwards by the bottom 4 .
  • the side body 10 can be made in one piece, as shown in FIG. 1 , or in several concentric ferrules.
  • the package 1 includes an external radiation protection shell 14 , peculiar to the present invention.
  • the shell 14 is made using the axial stack of a plurality of unitary annular structures 16 , for example provided in a number n between 10 and 50, over a cumulative height “H” of about 1 to 4 m.
  • This height “H” of the external shell 14 substantially corresponds to that of the housing 12 along the direction 8 .
  • all the structures 16 stacked along the axis 2 are identical, each of which is integral with and in contact with an external radial surface 18 of the side body 10 .
  • the last structure 16 can nevertheless be coated with a closing plate 20 .
  • FIGS. 3 to 5 the design of one of the unitary annular structures 16 , shown in its position as assumed when it is on the package in a vertical position, with the lid facing upwards as in FIGS. 1 and 2 , will be detailed.
  • the structure 16 is preferably made in one piece.
  • the annular structure 16 is made as a single piece, for example by forging and machining, or even by casting, preferably by iron casting. These techniques make it possible to limit production costs.
  • the structure 16 has a generally U-shaped half transverse cross-section with its base oriented upwards. A reverse orientation with the base pointing downwards would of course be contemplatable, without departing from the scope of the invention.
  • This half transverse cross-section retains a constant shape regardless of the cross-sectional plane along the circumferential direction of this structure 16 .
  • the U-base forms a radial heat conduction wall 22 . It assumes the shape of a straight line segment which is preferably orthogonal to the axis 2 , for a more direct conduction path to the outside of the package.
  • This wall 22 has the same thickness “E1” in any half transverse cross-section. This thickness “E1” is for example between 5 and 40 mm, preferentially between 15 and 25 mm. As will be described subsequently, its thickness is correlated with the number of structures 16 , in particular with the aim that all the radial walls together can discharge a determined quantity of heat released by the radioactive materials.
  • the internal end of the radial heat conduction wall 22 is to be in contact and integral with the external radial surface 18 of the side body 10 .
  • the radial wall 22 is integral with an outer annular wall 24 .
  • this wall 24 takes the form of a straight line segment parallel to axis 2 , projecting downwards from the external end of the radial wall 22 .
  • the thickness “E2” may be between 5 and 40 mm, and preferably between 15 and 25 mm.
  • the radial wall 22 is integral with an inner annular wall 26 forming a second U-branch.
  • the inner annular wall 26 is also in contact with and integral with the external radial surface 18 of the side body 10 .
  • the contact is preferably a surface contact over the entire inner surface of the annular internal wall 26 .
  • the securement is made, for example, by shrink-fitting, as will be described hereafter.
  • the contact can be simply a sliding contact between the inner annular wall 26 and the internal end of the radial heat conduction wall 22 which extends axially therefrom, on the one hand, and the external radial surface 18 of the side body 10 , on the other hand.
  • the wall 26 also takes the form of a straight segment parallel to the axis 2 , which projects downwards from the internal end of the radial wall 22 .
  • the thickness “E3” of the wall 26 is dictated in particular by its ability to limit gamma radiations. The greater its thickness, the more the thickness of the side body 10 can be reduced. The manufacturing costs of the assembly formed by the side body 10 and the external shell 14 can then be reduced, since the cost of the inner parts of the annular structures 16 , which are preferably made of cast iron, is lower than that of the body 10 , which is preferably made of forged steel.
  • each annular cavity 30 is delimited by two directly consecutive structures 16 in the stack.
  • the cavity 30 is radially closed outwards by the outer annular wall 24 of one of both directly consecutive annular structures 16 and radially closed inwards by the inner annular wall 26 of the same annular structure 16 .
  • annular cavity 30 is axially closed upwards by the radial wall 22 of this same structure 16 , and axially closed downwards by the radial wall 22 of the directly consecutive annular structure 16 in the stack, which seals the opening between the two U-branches of the first structure 16 .
  • the outer annular walls 24 are adjacent along the direction 8 , and form together an external radial surface of the package which is substantially continuous and easy to decontaminate.
  • the annular cavities 30 thus follow one another along the axis 2 , by being filled completely or almost completely with a radiation protection material.
  • this may be a material for protection against gamma radiation, and/or a neutron absorption material aiming at meeting regulatory radiological criteria about the package when it is loaded with radioactive materials.
  • a neutron absorption material comprising neutron absorbing elements on the one hand and hydrogen elements on the other hand.
  • neutron-absorbing elements it is intended elements with an effective cross-section greater than 100 barns for thermal neutrons.
  • these are elements of the boron, gadolinium, hafnium, cadmium, indium type, etc.
  • each structure 16 meets the following formula: 0.02 ⁇ n.E 1/ H ⁇ 0.3
  • this ratio allows sufficient neutron protection to be maintained in the cavities 30 . Moreover, by being higher than 0.02, this ratio surprisingly makes it possible to maintain the neutron protection material at a reasonable maximum temperature, limiting accelerated ageing risks. This ratio thus offers a very satisfactory compromise in terms of thermal conduction and neutron protection as a whole.
  • n.E1/H corresponds to the average thickness when it is not constant along the radial heat conduction wall 22 .
  • the package is such that it meets the following formula:
  • the thickness E1 of the radial walls 22 is limited and locally observed neutron leakage is thereby reduced.
  • each structure 16 preferably meets the following formula: L/E 1 ⁇ 10 with “L” corresponding to the radial spacing between the inner and outer annular walls 26 , 24 . It is additionally set out that this distance L preferably also substantially corresponds to the radial length of the neutron protection. More generally, it is stated that the annular cavity is filled entirely or largely by the neutron protection, preferably over at least 90% of its total volume.
  • This geometrical condition limits thickness E1 of the radial wall 22 , which is a determining factor for the neutron dose-equivalent rate at 2 metres.
  • a dimensioning of the annular structure 16 with such a ratio greater than or equal to 10 would result in a high radial length of the shell 14 to fulfil the neutron dose-equivalent rate criterion at 2 metres, and therefore a substantial overall mass of the package. This is at least partly explained by the fact that from a given radial length of the neutron protection, a threshold effect occurs and the increase in this length has only little effect on the neutron dose-equivalent rate at 2 metres.
  • the radiation protection material is, for example, in the form of one or more cast elements, preferably a single continuous ring cast over 360° in the cavity 30 .
  • it may be in the form of one or more prefabricated elements arranged in the cavity 30 .
  • a neutron protection ring 34 is discontinuously formed by means of several protection elements 32 arranged end-to-end.
  • these latter elements 32 preferably have circumferential overlapping areas 36 at their circumferential ends ensuring junction between these individual elements.
  • FIG. 6 represents a first method for manufacturing the package 1 , as for the steps relating to assembling the external radiation protection shell 14 around the side body 10 .
  • This method consists in repeating two successive steps.
  • the first of these two steps consists in installing one of the unitary annular structures 16 in the stack around the side body 10 , even though its annular cavity 30 is not yet filled with the radiation protection element(s).
  • This step is depicted by arrow 36 in FIG. 6 .
  • the structure 16 can be heated beforehand, for example to a temperature in the order of 200° C. It is brought into contact with the rest of the stack so as to close the cavity 30 of the structure 16 , which has been previously installed in the stack, and which is filled with the radiation protection material.
  • the structure has cooled down, e.g. to a temperature below 160° C., it adheres by shrink-fitting to the external radial wall 18 of the side body, via the internal end of the radial wall 22 and via the inner annular wall 26 .
  • the radiation protection material can then be installed in the annular cavity 30 of the structure 16 cooled without any risk of thermal degradation of this material.
  • these steps are carried out with the package 1 in a vertical position, but with its bottom oriented upwards so that each cavity 30 to be filled is open upwardly.
  • the material is installed by casting or by arranging prefabricated elements in the cavity 30 , then the radiation protection thus obtained is inspected before repeating these same two first and second steps.
  • FIG. 7 represents a second method for manufacturing the package 1 , as for the steps relating to assembling the external radiation protection shell 14 around the side body 10 .
  • This method consists in repeating two successive steps. The first of these two steps consists here in installing each radiation protection element in the annular cavity 30 partly defined by one of the unitary annular structures 16 , not yet installed in the stack. This step can advantageously be carried out on a different site from the one on which the stacking of the annular unit structures 16 is carried out. The quality of the radiation protection elements can be inspected before installing the structure 16 around the body 10 , this operation corresponding to the second step. This insertion of the structure 16 , equipped with its radiation protection, can also be carried out by heating, as described previously.
  • each unitary annular structure 16 has a generally U-shaped half transverse cross-section, with the U-base formed by the radial wall 22 , and the two U-branches formed respectively by the outer annular wall 24 and the inner annular wall 26 .
  • the two free ends of the two annular walls 24 , 26 lie in the same transverse plane of the package. Nevertheless, the free ends of the two annular walls 24 , 26 may be offset axially from each other without departing from the scope of the invention. Keeping the free ends of the two annular walls 24 , 26 in the same transverse plane makes it easier to cast the neutron protection into the annular cavity 30 .
  • FIG. 8 alternative embodiments are shown in which the half transverse cross-section of the structures is different.
  • this is an H whose central bar 22 is substantially orthogonal to the axis 2 , to form the radial heat conduction wall.
  • the two lateral H-branches are thus oriented along the direction 8 , and they take part in delimitating two directly consecutive annular cavities 30 , arranged on either side of the central bar 22 of this H.
  • each cavity 30 is radially delimited outwards by part of the outer wall 24 (the external lateral H-branch) of one of the structures 16 , and by part of the outer wall 24 of the structure 16 directly consecutive in the stack.
  • Each annular cavity 30 is also radially delimited inwards by part of the inner wall 26 (the internal lateral H-branch) of one of the structures 16 , and by part of the inner wall 26 of the structure 16 directly adjacent in the stack.
  • the two lateral branches could be axially offset from each other, without departing from the scope of the invention.
  • FIG. 9 represents another alternative embodiment previously discussed, in which the unitary structure 16 with a generally u-shaped half transverse cross-section no longer has a base 22 substantially orthogonal to the axis 2 , but this base 22 is tilted with respect to the same axis 2 by an angle “A” other than 90°. This angle can preferably be between 20 and 70°.
  • the base 22 forming the radial heat conduction wall can be a tilted straight line segment, connecting the ends of the two annular walls 24 , 26 .
  • a central part of this base 22 of the can be a straight segment, or even a curved portion, and the two connecting ends 40 can be rounded.
  • FIGS. 10 and 11 represent another alternative embodiment, in which the radial heat conduction wall 22 of each unitary annular structure 16 has a different shape. It is no longer straight and radial as in the previous embodiments, but comprises, in a half transverse cross-section, at least one axial level change 22 c between a wall radially outer portion 22 a and a wall radially inner portion 22 b.
  • This embodiment like the previous one, enables improvement of the radiation protection, as no radial leakage occurs via the radial heat conduction walls 22 .
  • the axial level change 22 c takes the form of a riser oriented parallel to axis 2 , and substantially centered between both portions 22 a , 22 b.
  • the axial offset observed between these two portions 22 a, 22 b is found between the annular portions 24 , 26 , so that when stacking structures 16 , the two-level radial wall 22 suitably seals the opening defined between the offset annular portions 24 , 26 of structure 16 previously installed in the stack.
US17/050,584 2018-04-27 2019-04-25 Packaging for the transport and/or storage of radioactive materials, permitting easier production and improved heat conductivity Active US11250961B2 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
FR1853746A FR3080705B1 (fr) 2018-04-27 2018-04-27 Emballage de transport et/ou d'entreposage de matieres radioactives permettant une fabrication facilitee ainsi qu'une amelioration de la conduction thermique
FR1853746 2018-04-27
PCT/FR2019/050976 WO2019207255A1 (fr) 2018-04-27 2019-04-25 Emballage de transport et/ou d'entreposage de matieres radioactives permettant une fabrication facilitee ainsi qu'une amelioration de la conduction thermique

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US20210241932A1 US20210241932A1 (en) 2021-08-05
US11250961B2 true US11250961B2 (en) 2022-02-15

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US (1) US11250961B2 (fr)
EP (1) EP3766082B1 (fr)
JP (1) JP7200263B2 (fr)
KR (1) KR102638259B1 (fr)
CN (1) CN112041941B (fr)
ES (1) ES2914389T3 (fr)
FR (1) FR3080705B1 (fr)
SI (1) SI3766082T1 (fr)
WO (1) WO2019207255A1 (fr)

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59182396A (ja) 1983-03-31 1984-10-17 三井造船株式会社 使用済核燃料輸送容器の製造方法
EP1524673A1 (fr) 2002-07-23 2005-04-20 Mitsubishi Heavy Industries, Ltd. Chateau de transport et son procede de production
US20080031396A1 (en) * 2006-06-30 2008-02-07 Krishna Singh Spent fuel basket, apparatus and method using the same for storing high level radioactive waste
US20140044227A1 (en) * 2012-08-13 2014-02-13 Transnuclear, Inc. Composite basket assembly
JP2014228343A (ja) 2013-05-21 2014-12-08 朱雀プラスチック株式会社 放射能汚染物の収納容器
US20150206610A1 (en) * 2014-01-22 2015-07-23 Nac International, Inc. Systems and methods for passive cooling during nuclear fuel transfer
US20200182517A1 (en) * 2017-08-15 2020-06-11 Jan Vetrovec Magnetocaloric refrigerator

Family Cites Families (28)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2085189A1 (en) * 1970-01-14 1971-12-24 Transnucleaire Storage and transport container for a - radioactive materials
JPS59210397A (ja) * 1983-05-14 1984-11-29 株式会社日本製鋼所 使用済核燃料輸送容器
US4535250A (en) * 1984-05-30 1985-08-13 The United States Of America As Represented By The United States Department Of Energy Container for radioactive materials
JPH0298700A (ja) * 1988-10-06 1990-04-11 Mitsubishi Heavy Ind Ltd 放射性物質輸送用容器
US5406600A (en) * 1993-10-08 1995-04-11 Pacific Nuclear Systems, Inc. Transportation and storage cask for spent nuclear fuels
FR2776118B1 (fr) * 1998-03-13 2000-06-09 Transnucleaire Dispositif de protection contre les rayonnements pour conteneur de transport de matieres radioactives
FR2786309B1 (fr) * 1998-11-23 2001-01-26 Transp S De L Ind Nucleaire Tr Dispositif amortisseur de chocs pour conteneurs de matieres radioactives
ES2181339T3 (es) * 1999-06-19 2003-02-16 Gnb Gmbh Recipiente de transporte y/o almacenamiento para elementos radiactivos productores de calor.
EP1122745A1 (fr) * 1999-12-15 2001-08-08 GNB Gesellschaft für Nuklear-Behälter mbH Conteneur pour le transport et/ou le stockage de matières radioactives dégageant de la chaleur et procédé de fabrication d'un tel conteneur
JP3416657B2 (ja) * 2001-01-25 2003-06-16 三菱重工業株式会社 キャスクおよびキャスクの製造方法
JP2003057386A (ja) * 2001-08-13 2003-02-26 Toshiba Corp 使用済燃料貯蔵装置、その製造方法、及び使用済燃料の貯蔵方法
US7068748B2 (en) * 2004-03-18 2006-06-27 Holtec International, Inx. Underground system and apparatus for storing spent nuclear fuel
FR2872956B1 (fr) * 2004-07-12 2006-11-17 Cogema Logistics Sa Dispositif externe d'evacuation de chaleur pour emballage destine au stockage et/ou au transport de matieres nucleaires
EP1854103A1 (fr) * 2005-02-12 2007-11-14 Kyung Yeon Jo Appareil pour stocker des dechets nucleaires, procede pour le fabriquer et l'installer
US7994380B2 (en) * 2006-10-11 2011-08-09 Holtec International, Inc. Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow
CA2673281C (fr) * 2006-12-11 2012-07-10 Single Buoy Moorings Inc. Conduit flexible de transfert de fluide cryogenique comprenant une couche isolante fibreuse et procede de construction d'un tel conduit de transfert
FR2914104B1 (fr) * 2007-03-21 2012-05-04 Tn Int Emballage pour le transport et/ou stockage de matieres nucleaires comprenant une protection radiologique en plomb coule sur une armature metallique
DE102007024903B4 (de) * 2007-05-29 2009-05-07 Pyreos Ltd. Vorrichtung mit Sandwichstruktur zur Detektion von Wärmestrahlung, Verfahren zum Herstellen und Verwendung der Vorrichtung
US8995604B2 (en) * 2009-11-05 2015-03-31 Holtec International, Inc. System, method and apparatus for providing additional radiation shielding to high level radioactive materials
FR2961005B1 (fr) * 2010-06-02 2015-12-11 Tn Int Emballage pour le transport et/ou entreposage de matieres radioactives, comprenant des moyens de conduction thermique ameliores
CN202093844U (zh) * 2010-12-01 2011-12-28 中国核电工程有限公司 用于放射性物质运输容器的多功能散热结构
FR2974228B1 (fr) * 2011-04-18 2013-06-07 Tn Int Element de conduction thermique permettant d'ameliorer la fabrication d'un emballage de transport et/ou d'entreposage de matieres radioactives
FR2985365B1 (fr) * 2011-12-29 2014-01-24 Tn Int Conducteur thermique pour corps lateral d'emballage de transport et/ou d'entreposage de matieres radioactives
JP3174865U (ja) * 2012-01-30 2012-04-12 秀一 富田 収納容器
FR3006098B1 (fr) * 2013-05-22 2015-06-26 Tn Int Emballage d'entreposage de combustible irradie comprenant des rails amortis de guidage d'etui
WO2017165180A1 (fr) * 2016-03-22 2017-09-28 Holtec International Appareil permettant de stocker et/ou de transporter des matières radioactives
FR3049756B1 (fr) * 2016-04-01 2020-06-12 Tn International Emballage de transport et/ou d'entreposage de matieres radioactives equipe de dispositifs de dissipation de chaleur realises d'un seul tenant
CN107481777A (zh) * 2017-07-07 2017-12-15 中国核电工程有限公司 一种核燃料组件容器用带有散热功能的屏蔽结构

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59182396A (ja) 1983-03-31 1984-10-17 三井造船株式会社 使用済核燃料輸送容器の製造方法
EP1524673A1 (fr) 2002-07-23 2005-04-20 Mitsubishi Heavy Industries, Ltd. Chateau de transport et son procede de production
US20080031396A1 (en) * 2006-06-30 2008-02-07 Krishna Singh Spent fuel basket, apparatus and method using the same for storing high level radioactive waste
EP2041753B1 (fr) 2006-06-30 2013-10-09 Holtec International, Inc. Appareil, système et procédé de stockage de déchets de haut niveau
US20140044227A1 (en) * 2012-08-13 2014-02-13 Transnuclear, Inc. Composite basket assembly
JP2014228343A (ja) 2013-05-21 2014-12-08 朱雀プラスチック株式会社 放射能汚染物の収納容器
US20150206610A1 (en) * 2014-01-22 2015-07-23 Nac International, Inc. Systems and methods for passive cooling during nuclear fuel transfer
US20200182517A1 (en) * 2017-08-15 2020-06-11 Jan Vetrovec Magnetocaloric refrigerator

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
International Search Report for Application No. PCT/FR2019/050976 dated Sep. 12, 2019.
Search Report issued in French Patent Application No. 1853746 dated Dec. 4, 2018.
Written Opinion for PCT/FR2019/050976 dated Sep. 12, 2019.

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KR20210003760A (ko) 2021-01-12
CN112041941B (zh) 2024-03-01
US20210241932A1 (en) 2021-08-05
EP3766082B1 (fr) 2022-03-23
JP7200263B2 (ja) 2023-01-06
CN112041941A (zh) 2020-12-04
EP3766082A1 (fr) 2021-01-20
WO2019207255A1 (fr) 2019-10-31
JP2021522472A (ja) 2021-08-30
KR102638259B1 (ko) 2024-02-19

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